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Catalog of Programs in Category K
K. Reactor Systems Analysis
| psr-0315 | AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5 |
| ccc-0519 | AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors |
| ccc-0459 | BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |
| nesc0387 | CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search |
| ccc-0643 | CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC |
| ccc-0650 | DOORS, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport |
| uscd1234 | DRAGON 3.05D, Reactor Cell Calculation System with Burnup |
| ccc-0647 | DRAGON, Reactor Cell Calculation System with Burnup |
| nesc0784 | DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant |
| nea-1683 | ERANOS 2.0, Modular code and data system for fast reactor neutronics analyses |
| nea-1265 | HERMES-KFA, High-Energy Radiation Transport by Monte-Carlo |
| ests0003 | IRRAS, Integrated Reliability and Risk Analysis System for PC |
| nea-0624 | JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR |
| iaea1232 | LABAN-PEL, 2-D MultiGroup Neutron Diffusion in X-Y Geometry by Response Matrix Eigenvalue |
| psr-0355 | NJOY-94, General ENDF/B Processing System for Reactor Design Problems |
| psr-0171 | NJOY91, General ENDF/B Processing System for Reactor Design Problems |
| nea-1238 | PASC-1, Petten AMPX-II/SCALE-3 Code System for Reactor Neutronics Calculation |
| nea-0615 | RELOSS, Reliability of Safety System by Fault Tree Analysis |
| iaea0969 | RHEIN, Modular System for Reactor Design Calculation |
| nea-0598 | RSYST, Modular System for Reactor Core and Shielding Problems |
| psr-0405 | SAPHIRE 7.27, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations |
| ccc-0785 | SCALE 6.1, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics |
| ccc-0248 | SWAN-PPL, Fusion Reactor 1-D Particle Transport Optimization |
| iaea1370 | TRIGLAV, Research Reactor Calculations |
| uscd1239 | VENTEASY, Criticality search for a desired Keffective by adjusting dimensions, nuclide concentrations, or buckling |
| ccc-0654 | VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup |
| iaea0871 | VPI-NECM, Nuclear Engineering Program Collection for College Training |
| nea-0655 | VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation |
| dlc-0142 | ZZ KERMAL, Neutron and Gamma Kerma Library from ENDL and EGDL |